Constitutive material model for the prediction of stresses in irradiated anisotropic graphite components
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference5 articles.
1. The development of a stress analysis code for nuclear graphite components in gas-cooled reactors
2. ABAQUS, Hibbit, Karlsonn and Sorensen, 2006.
3. Analysis of the dimensional changes and structural changes in polycrystalline graphite under fast neutron irradiation
4. Graphite thermal expansion relationship for different temperature ranges
5. UKAEA Reactor Group studies of irradiation-induced creep in graphite
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